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ML19269D918
Show incoming properties
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
Accession number
ML19269D918  +
Atomic Element
Iodine +, Hydrogen +  and Lead +
Committee
Advisory Committee on Reactor Safeguards +
Cornerstone
Mitigating Systems +
Docket
05000320  +, 05000556  +, 05000557  +, 00556  +  and 00557  +
From
Fate M +  and PUBLIC SERVICE CO. OF OKLAHOMA +
General design criterion
GDC 10 +
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ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +, ML19269D918 +  and ML19269D918 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
Issue date
June 15, 1979  +
Manufacturer
General Electric +
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11:38:54, 3 January 2025  +
NRC bulletin
NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +
NUREG
NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +
Page count
80  +
Person
May Ma +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +  and Regulatory Guide 1.8 +
Site
Crane +  and Black Fox +
Start date
June 15, 1979  +
State
Texas +, Illinois +, Maryland +, Washington +, Oklahoma +  and Missouri +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Safety Relief Valve +, Main Condenser +, Containment Spray +  and Low Pressure Coolant Injection +
Title
Describes Technical Advisory Committee Program to Assess TMI-2 Events & Apply Lessons Learned.Tasks Included Assuring Containment Isolation & Identifying Sys Used in Transfer of Radioactive Fluid  +
To
Harold Denton +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Fuel cladding +  and Core Exit Thermocouple +
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http://pbadupws.nrc.gov/docs/ML1926/ML19269D918.pdf  +
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